ML20080K015
| ML20080K015 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/20/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9502280271 | |
| Download: ML20080K015 (3) | |
Text
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'u February 20,1995 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission -
Washington, D.C. 20555.
- Attn: Document Control Desk
Subject:
Errata to WCAP-14273 and WCAP-14274 Byron and Braidwood Nuclear Power Stations NRC Docket Numbers 50-454 and 50-456 3
References:
1.
D. Saccomando letter to NRC dated February 13,1995, transmitting Technical Specification Amendment with regards to Increase of the Interim Plugging Criteria (IPC) for Byron and Braidwood Unit 1 Steam Generators 2.
D. Saccomando letter to NRC dated February 7,1995, transmitting WCAP-14273, " Technical Support for Alternate Plugging Criteria with Tube Expansion at Tube Support Plate Intersections for Braidwood-1 and Byron-1 Model D4 Steam Generators" e
Reference 2 transmitted WCAP-14273, " Technical Support for Alternate Plugging Criteria with Tube Expansion at Tube Support Plate Intersections for Braidwood-1 and Byron-1 Model D4 Steam Generators (Proprietary)." The non-proprietary version, WCAP-14274, was transmitted in Reference 1. Since the time of their issuance, errata sheets for these WCAPs have been issued. The errata clarifies the relationship of the text to the reference j
figures and does not alter the technical content of the report. Attached are errata sheets for both the proprietary and non-proprietary versions.
If you have any questions concerning this correspondence, please contact this office.
- incerely, hd
%dv Denise M. Saccomando Nuclear Licensing Administrator i
Attachment cc:
D. Lynch, Senior Project Managers-NRR R. Assa, Braidwood Project Managers-NRR l
G. Dick, Byron Project Manager-NRR J. Martin, Regional Administrator-RIII S. DuPont, Senior Resident Inspector-Braidwood H. Peterson, Senior Resident Inspector-Byron Office of Nuclear Safety-IDNS muwtve.to.ns.rr.t.
9502280271 950220 8
l PDR ADOCK 05000454
r NP6
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b ERRATA SHEET for WCAP 14273 Dtd 2/95 - Taehaleil Sunoort for Alternate Ptuo in Criteria with Tube Ernanaion at Tube Sunnart Plate Internae+ ions for Braidwood - 1 and Byron - 1 Model D4 Steam
~
Generators The following changes have been made to Section 9 of the subject report for the purpose of clarifying the relationship of the text to the reference figures. The changes do not alter the technical content of the report.
i Eags Reads Should read 9-8 Para 3, line 8 Figure 9-7 Figure 9-6 9-10 Para 1,line 4 Figure 9-8 Figure 9-7 9-10 Para 2,line 1 Figure 9-8 Figure 9-7 9-10 Para 2, line 2 Figure 9-5 Figure 9-6 9-10 Para 2, line 5 Figure 9-9 Figure 9-8 9-13 Para 8,line 1 Figure 9-8 Figure 9-9 J
9-14 Para 4,line 1 Figure 9-8 Figure 9-9 9-14 Para 4, line 7 Figure 9-8 Figure 9-9 9-14 Para 5, line 1 Figure 9-8 Figure 9-9 9-14 Para 5,line 6 Figure 9-9 Figure 9-10 9-15 Para 3,line 1 Figure 9-8 Figure 9-9 9-15 Para 3, line 3 Figure 9-8 Figure 9-9 i
I
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ERRATA SHEET for WCAP 14274 Dtd 2/95 - Tachaical Suoport for Alternmea Pliinalaa Criteria with Tube hamanina at Tube Support Plate Inter =ac'inan for Braidwood - 1 mad Byron - 1 MW D4 Stamm Generators The following changes have been made to Section 9 of the subject report for the purpose of clarifying the relationship of the text to the reference figures The changes do not alter the tacWat content of the report.
East Ennda Should read 9-8 Para 3, line 8 Figure 9-7 Figure 9-6 9-10 Para 1, line 4 Figure 9-8 Figure 9-7 9-10 Para 2, line 1 Figure 9-8 Figure 9-7 i
9-10 Para 2, line 2 Figure 9-5 Figure 9-6 9-10 Para 2, line 5 Figure 9-9 Figure 9-8 9-13 Para 8,line 1 Figure 9-8 Figure 9-9 9-14 Para 4, line 1 Figure 9-8 Figure 9-9 9-14 Para 4, line 7 Figure 9-8 Figure 9-9 l
9-14 Para 5, line 1 Figure 9-8 Figure 9-9 9-14 Para 5, line 6 Figure 9-9 Figure 9-10 9-15 Para 3, line 1 Figure 9-8 Figure 9-9 9-15 Para 3, line 3 Figure 9-8 Figure 9-9 l
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